[1]
|
Petti, D.A., Demkowicz, P.A., Maki, J.T., et al. (2012) TRISO-Coated Particle Fuel Performance. Comprehensive Nuclear Materials, 3, 151-213. https://doi.org/10.1016/B978-0-08-056033-5.00055-0
|
[2]
|
Li, R., Liu, B. and Verfondern, K. (2019) The Study of Irradiation Induced Failure Behavior for the TRISO-Coated Fuel Particle in HTGR. Journal of Nuclear Materials, 516, 214-227. https://doi.org/10.1016/j.jnucmat.2019.01.029
|
[3]
|
Besmann, T.M., Stoller, R.E., Samolyuk, G., et al. (2012) Modeling Deep Burn TRISO Particle Nuclear Fuel. Journal of Nuclear Materials, 430, 181-189. https://doi.org/10.1016/j.jnucmat.2012.06.041
|
[4]
|
Yang, X.Y., Lu, Y. and Zhang, P. (2015) First-Principles Study of Native Point Defects and Diffusion Behaviors of Helium in Zirconium Carbide. Journal of Nuclear Materials, 46, 161. https://doi.org/10.1016/j.jnucmat.2015.06.008
|
[5]
|
Collin, B.P. (2013) Modeling and Analysis of FCM UN TRISO Fuel Using the PARFUME Code. INL/EXT-13-30193.
|
[6]
|
Choi, Y. and Lee, J.K. (2006) An Analytical Model for the Amoeba Effect in UO2 Fuel Pellets. Journal of Nuclear Materials, 357, 213-220. https://doi.org/10.1016/j.jnucmat.2006.05.053
|
[7]
|
Porter, I.E., Knight, T.W., Dulude, M.C., et al. (2013) Design and Fabrication of an Advanced TRISO Fuel with ZrC Coating. Nuclear Engineering and Design, 259, 180-186. https://doi.org/10.1016/j.nucengdes.2013.03.004
|
[8]
|
Wang, F.W., Chen, L., Wang, Y.J., et al. (2017) Effect of Deposition Time on Growth of ZrC-SiC Composite Coating Synthesized by Low Pressure Chemical Vapor Deposition. Ceramics International, 43, 2853-2858.
https://doi.org/10.1016/j.ceramint.2016.10.187
|
[9]
|
Ma, X., Chen, S.A., Mei, M., et al. (2017) Influence of Total Pressure on the Microstructures and Growth Mechanism of ZrC Coatings Prepared by Chemical Vapor Deposition from the Zr-Br2-C3H6-H2-Ar System. Ceramics International, 43, 3501-3509. https://doi.org/10.1016/j.ceramint.2016.10.172
|
[10]
|
Kim, D.J., Ko, M.J., Park, J.Y., et al. (2014) Influence of Free Carbon on the Characteristics of ZrC and Deposition of Near-Stoichiometric ZrC in TRISO Coated Particle Fuel. Journal of Nuclear Materials, 451, 97-103.
https://doi.org/10.1016/j.jnucmat.2014.03.045
|
[11]
|
Vasudevamurthy, G., Katoh, Y., Aihara, J., et al. (2015) Microstructure and Mechanical Properties of Heat-Treated and Neutron Irradiated TRISO-ZrC Coatings. Journal of Nuclear Materials, 464, 245-255.
https://doi.org/10.1016/j.jnucmat.2015.04.026
|
[12]
|
Minato, K. and Ogawa, T. (2003) Research and Development of ZrC-Coated Particle Fuel. Proceedings of GLOBAL, New Orleans, 16-20 November 2003, 142. https://doi.org/10.1299/jsmeicone.2003.142
|
[13]
|
Biira, S., Crouse, P.L., Bissett, H., et al. (2017) Optimisation of the Synthesis of ZrC Coatings in a Radio Frequency Induction-Heating Chemical Vapour Deposition System Using Response Surface Methodology. Thin Solid Films, 624, 61-69.
https://doi.org/10.1016/j.tsf.2017.01.018
|
[14]
|
Liu, B., Liu, C., Shao, Y.L., et al. (2012) Deposition of ZrC-Coated Particle for HTR with ZrCl4 Powder. Nuclear Engineering and Design, 251, 349-353. https://doi.org/10.1016/j.nucengdes.2011.10.012
|
[15]
|
Biira, S., Crouse, P.L., Bissett, H., et al. (2017) The Role of ZrCl4 Partial Pressure on the Growth Characteristics of Chemical Vapour Deposited ZrC Layers. Ceramics International, 43, 15133-15140.
https://doi.org/10.1016/j.ceramint.2017.08.042
|
[16]
|
Ueta, S., Aihara, J., Yasuda, A., et al. (2008) Fabrication of Uniform ZrC Coating Layer for the Coated Fuel Particle of the Very High Temperature Reactor. Journal of Nuclear Materials, 376, 146-151.
https://doi.org/10.1016/j.jnucmat.2008.02.068
|
[17]
|
Aihara, J., Ueta, S., Honda, M., et al. (2019) Microstructures of ZrC Coated Kernels for Fuel of Pu-Burner High Temperature Gas-Cooled Reactor in Japan. Journal of Nuclear Materials, 522, 32-40.
https://doi.org/10.1016/j.jnucmat.2019.05.012
|
[18]
|
Ogava, T. and Ikawa, K. (1999) High-Temperature Heating Experiments on Unirradiated ZrC-Coated Fuel Particles. Journal of Nuclear Materials, 99, 85-93.
https://doi.org/10.1016/0022-3115(81)90141-0
|
[19]
|
Ogawa, T., Fukuda, K., Kashimura, S., et al. (1992) Performance of ZrC-Coated Particle Fuel in Irradiation and Postirradiation Heating Tests. Journal of the American Ceramic Society, 75, 2985-2990.
https://doi.org/10.1111/j.1151-2916.1992.tb04375.x
|
[20]
|
Minato, K., Ogawa, T., Fukuda, K., et al. (1995) Fission Product Release from ZrC-Coated Fuel Particles during Postirradiation Heating at 1600 ˚C. Journal of Nuclear Materials, 224, 85-92.
https://doi.org/10.1016/0022-3115(95)00032-1
|
[21]
|
Minato, K., Ogawa, T., Fukuda, K., et al. (1997) Fission Product Release from ZrC-Coated Fuel Particles during Post-Irradiation Heating at 1800˚C and 2000˚C. Journal of Nuclear Materials, 249, 142-149.
https://doi.org/10.1016/S0022-3115(97)00223-7
|
[22]
|
Chernikov, A. and Kosukhin, V. (2008) Deposition of ZrC Coats on UO2 Particles Using the Chloride Process. Nuclear Engineering and Design, 238, 2861-2865. https://doi.org/10.1016/j.nucengdes.2008.01.025
|
[23]
|
Katoh, Y., Vasudevamurthy, G., Nozawa, T., et al. (2013) Properties of Zirconium Carbide for Nuclear Fuel Applications. Journal of Nuclear Materials, 441, 718-742. https://doi.org/10.1016/j.jnucmat.2013.05.037
|
[24]
|
Shimada, S. (1997) Microstructural Observation of ZrO2 Scales Formed by Oxidation of ZrC Single Crystals with Formation of Carbon. Solid State Ionics, 101, 749-753. https://doi.org/10.1016/S0167-2738(97)00326-3
|
[25]
|
Gasparrini, C., Podor, R., Horlait, D., et al. (2017) Zirconium Carbide Oxidation: Maltese Cross Formation and Interface Characterization. Oxidation of Metals, 88, 509-519. https://doi.org/10.1007/s11085-016-9672-6
|
[26]
|
Jackson, H.F. and Lee, W.E. (2012) Properties and Characteristics of ZrC. Comprehensive Nuclear Materials, 2, 339-372. https://doi.org/10.1016/B978-0-08-056033-5.00023-9
|
[27]
|
Zheng, M.J., Szlufarska, I. and Morgan, D. (2015) Defect Kinetics and Resistance to Amorphization in Zirconium Carbide. Journal of Nuclear Materials, 457, 343-351. https://doi.org/10.1016/j.jnucmat.2014.11.059
|
[28]
|
Jiang, M., Zheng, J.W., Xiao, H.Y., et al. (2017) A Comparative Study of the Mechanical and Thermal Properties of Defective ZrC, TiC and SiC. Scientific Reports, 7, Article No. 9344. https://doi.org/10.1038/s41598-017-09562-x
|
[29]
|
Yang, Y., Lo, W.Y., Dickerson, C., et al. (2014) Stoichiometry Effect on the Irradiation Response in the Microstructure of Zirconium Carbides. Journal of Nuclear Materials, 454, 130-135.
https://doi.org/10.1016/j.jnucmat.2014.07.071
|
[30]
|
Yang, Y., Dickerson, C.A., Swoboda, H., et al. (2008) Microstructure and Mechanical Properties of Proton Irradiated Zirconium Carbide. Journal of Nuclear Materials, 378, 341-348. https://doi.org/10.1016/j.jnucmat.2008.06.042
|
[31]
|
Snead, L.L., Katoh, Y. and Kondo, S. (2010) Effects of Fast Neutron Irradiation on Zirconium Carbide. Journal of Nuclear Materials, 399, 200-207.
https://doi.org/10.1016/j.jnucmat.2010.01.020
|
[32]
|
Gosset, D., Dollé, M. and Simeone, D. (2008) Structural Evolution of Zirconium Carbide under Ion Irradiation. Journal of Nuclear Materials, 373, 123-129. https://doi.org/10.1016/j.jnucmat.2007.05.034
|
[33]
|
Gan, J., Yang, Y., Clayton, D., et al. (2009) Proton Irradiation Study of GFR Candidate Ceramics. Journal of Nuclear Materials, 389, 317-325.
https://doi.org/10.1016/j.jnucmat.2009.02.021
|
[34]
|
Christopher, J.U., Arthur, T.M. and Mark, A.K. (2015) In Situ Ion Irradiation of Zirconium Carbide. Journal of Nuclear Materials, 466, 606-614.
https://doi.org/10.1016/j.jnucmat.2015.08.009
|
[35]
|
Gosset, D., Dollé, M., Simeone, D., et al. (2008) Structural Behaviour of Nearly Stoichiometric ZrC under Ion Irradiation. Nuclear Instruments and Methods in Physics Research B, 266, 2801-2805.
https://doi.org/10.1016/j.nimb.2008.03.121
|
[36]
|
Motta, A. (2013) Understanding the Irradiation Behavior of Zirconium Carbide. DOE-NEUP 10-679, the Pennsylvania State University, State College. https://doi.org/10.2172/1097003
|
[37]
|
Huang, Y., Maier, B.R. and Allen, T.R. (2014) Irradiation-Induced Effects of Proton Irradiation on Zirconium Carbides with Different Stoichiometries. Nuclear Engineering and Design, 277, 55-63.
https://doi.org/10.1016/j.nucengdes.2014.06.001
|
[38]
|
Snead, L.L., Nozawa, T., Katoh, Y., Byun, et al. (2007) Handbook of SiC Properties for Fuel Performance Modeling. Journal of Nuclear Materials, 371, 329-377. https://doi.org/10.1016/j.jnucmat.2007.05.016
|
[39]
|
Minato, K., Ogawa, T., Sawa, K., et al. (2000) Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors. Nuclear Technology, 130, 272-384. https://doi.org/10.13182/NT00-A3093
|
[40]
|
Minato, K., Ogawa, T., Koya, T., et al. (2000) Retention of Fission Product Caesium in ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors. Journal of Nuclear Materials, 279, 181-188.
https://doi.org/10.1016/S0022-3115(00)00015-5
|
[41]
|
Wongsawaeng, D. (2010) Performance Modeling of Deep Burn TRISO Fuel Using ZrC as a Load-Bearing Layer and an Oxygen Getter. Journal of Nuclear Materials, 396, 149-158. https://doi.org/10.1016/j.jnucmat.2009.10.065
|
[42]
|
Maier, B., Yang, Y.K. and Allen, T.R. (2016) Silver Diffusivity Measurement in ZrC with SIMS to Study the Release Behavior of 110mAg for Nuclear Fuel Applications. Journal of Nuclear Materials, 478, 135-143.
https://doi.org/10.1016/j.jnucmat.2016.06.010
|
[43]
|
Yang, Y.K. and Allen, T.R. (2016) The Measurement of Silver Diffusivity in Zirconium Carbide to Study the Release Behavior of 110mAg in the ZrC TRISO-Coated Nuclear Fuel Particle. Journal of Nuclear Materials, 470, 76-83.
https://doi.org/10.1016/j.jnucmat.2015.12.010
|
[44]
|
Kim, S., Szlufarska, I. and Morgan, D. (2010) Ab Initio Study of Point Defect Structures and Energetics in ZrC. Journal of Applied Physics, 107, Article ID: 053521. https://doi.org/10.1063/1.3309765
|
[45]
|
Zhao, H.S., Liu, B., Zhang, K.H. and Tang, C.H. (2013) Microstructure Analysis of Zirconium Carbide Layer on Pyrocarbon-Coated Particles Prepared by Zirconium Chloride Vapor Method. Nuclear Engineering and Design, 251, 443-448.
https://doi.org/10.1016/j.nucengdes.2011.10.001
|
[46]
|
Liu, M.L., Liu, B. and Shao, Y.L. (2012) Optimization of the UO2 Kernel Coating Process by 2D Simulation of Spouted Bed Dynamics in the Coater. Nuclear Engineering and Design, 251, 124-130.
https://doi.org/10.1016/j.nucengdes.2011.10.062
|
[47]
|
Sun, W., Hao, Z.H. and Xiong, X. (2013) Thermodynamic Analysis and Growth of Zirconium Carbide by Chemical Vapor Deposition. Physics Procedia, 46, 88-101. https://doi.org/10.1016/j.phpro.2013.07.049
|